TY - JOUR
T1 - Core-Pedestal Plasma Configurations in Advanced Tokamaks
AU - Hassan, Ehab
AU - Kessel, C. E.
AU - Park, J. M.
AU - Elwasif, W. R.
AU - Whitfield, R. E.
AU - Kim, K.
AU - Snyder, P. B.
AU - Batchelor, D. B.
AU - Bernholdt, D. E.
AU - Cianciosa, M. R.
AU - Green, D. L.
AU - Law, K. J.H.
N1 - Publisher Copyright:
© 2023 Oak Ridge National Laboratory.
PY - 2023
Y1 - 2023
N2 - Several configurations for the core and pedestal plasma are examined for a predefined tokamak design by implementing multiple heating/current drive (H/CD) sources to achieve an optimum configuration of high fusion power in a noninductive operation while maintaining an ideally magnetohydrodynamic (MHD) stable core plasma using the IPS-FASTRAN framework. IPS-FASTRAN is a component-based lightweight coupled simulation framework that is used to simulate magnetically confined plasma by integrating a set of high-fidelity codes to construct the plasma equilibrium (EFIT, TOQ, and CHEASE), calculate the turbulent heat and particle transport fluxes (TGLF), model various H/CD systems (TORIC, TORAY, GENRAY, and NUBEAM), model the pedestal pressure and width (EPED), and estimate the ideal MHD stability (DCON). The TGLF core transport model and EPED pedestal model are used to self-consistently predict plasma profiles consistent with ideal MHD stability and H/CD (and bootstrap) current sources. In order to evaluate the achievable and sustainable plasma beta, varying configurations are produced ranging from the no-wall stability to with-wall stability regimes, simultaneously subject to the self-consistent TGLF, EPED, and H/CD source profile predictions that optimize configuration performance. The pedestal density, plasma current, and total injected power are scanned to explore their impact on the target plasma configuration, fusion power, and confinement quality. A set of fully noninductive scenarios are achieved by employing ion-cyclotron, neutral beam injection, helicon, and lower-hybrid H/CDs to provide a broad profile for the total current drive in the core region for a predefined tokamak design. These noninductive scenarios are characterized by high fusion gain (Q ~ 4) and power (Pfus ~ 600 MW), optimum confinement quality (H98 ~ 1.1), and high bootstrap current fraction (fBS ~ 0.7) for Greenwald fraction below unity. The broad current profile configurations identified are stable to low-n kink modes either because the normalized pressure β (Formula presented.) is below the no-wall limit or a wall is present.
AB - Several configurations for the core and pedestal plasma are examined for a predefined tokamak design by implementing multiple heating/current drive (H/CD) sources to achieve an optimum configuration of high fusion power in a noninductive operation while maintaining an ideally magnetohydrodynamic (MHD) stable core plasma using the IPS-FASTRAN framework. IPS-FASTRAN is a component-based lightweight coupled simulation framework that is used to simulate magnetically confined plasma by integrating a set of high-fidelity codes to construct the plasma equilibrium (EFIT, TOQ, and CHEASE), calculate the turbulent heat and particle transport fluxes (TGLF), model various H/CD systems (TORIC, TORAY, GENRAY, and NUBEAM), model the pedestal pressure and width (EPED), and estimate the ideal MHD stability (DCON). The TGLF core transport model and EPED pedestal model are used to self-consistently predict plasma profiles consistent with ideal MHD stability and H/CD (and bootstrap) current sources. In order to evaluate the achievable and sustainable plasma beta, varying configurations are produced ranging from the no-wall stability to with-wall stability regimes, simultaneously subject to the self-consistent TGLF, EPED, and H/CD source profile predictions that optimize configuration performance. The pedestal density, plasma current, and total injected power are scanned to explore their impact on the target plasma configuration, fusion power, and confinement quality. A set of fully noninductive scenarios are achieved by employing ion-cyclotron, neutral beam injection, helicon, and lower-hybrid H/CDs to provide a broad profile for the total current drive in the core region for a predefined tokamak design. These noninductive scenarios are characterized by high fusion gain (Q ~ 4) and power (Pfus ~ 600 MW), optimum confinement quality (H98 ~ 1.1), and high bootstrap current fraction (fBS ~ 0.7) for Greenwald fraction below unity. The broad current profile configurations identified are stable to low-n kink modes either because the normalized pressure β (Formula presented.) is below the no-wall limit or a wall is present.
KW - Core pedestal
KW - IPS-FASTRAN
KW - integrated modeling
KW - plasma confinement
KW - scenario development
UR - http://www.scopus.com/inward/record.url?scp=85152385197&partnerID=8YFLogxK
U2 - 10.1080/15361055.2022.2145826
DO - 10.1080/15361055.2022.2145826
M3 - Article
AN - SCOPUS:85152385197
SN - 1536-1055
VL - 79
SP - 189
EP - 212
JO - Fusion Science and Technology
JF - Fusion Science and Technology
IS - 3
ER -